Event Notification Report for June 29, 2007
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/28/2007 - 06/29/2007
EVENT NUMBERS
434584346943460434614346243464
Power Reactor
Event Number: 43458
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DAVE HELD
HQ OPS Officer: PETE SNYDER
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DAVE HELD
HQ OPS Officer: PETE SNYDER
Notification Date: 06/29/2007
Notification Time: 00:20 [ET]
Event Date: 06/29/2007
Event Time: 00:14 [EDT]
Last Update Date: 06/29/2007
Notification Time: 00:20 [ET]
Event Date: 06/29/2007
Event Time: 00:14 [EDT]
Last Update Date: 06/29/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RAY POWELL (R1)
RAY POWELL (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
RADIATION MONITORING INFORMATION TO ERDS AND SPDS WILL BE UNAVAILABLE DURING PLANNED UPGRADE TO THE SYSTEM.
"The computer servers which supply radiation monitoring information to the ERDS (Emergency Response Data System) and SPDS (Safety Parameter Display System) systems will be taken out of service to implement a planned upgrade. The servers are being replaced with upgraded models and are expected to be out of service for approximately 4 to 8 hours. The ability of radiation monitors to alarm in the control room will be unavailable while the servers are being replaced. The in plant radiation monitoring skids will be unaffected, as will any automatic actions generated by the monitors. The safety related radiation monitor displays in the control room will also remain available. As a compensatory measure while both servers are unavailable, a dedicated radiation protection technician will monitor the in plant radiation monitor skids to update the control room if anomalous indications are observed. In addition, operations will record the safety related radiation monitor readings every 2 hours.
"This is an 8 hour reportable event per 10CFR50.72(b)(3)(xiii), Major Loss of Assessment Capability. The operations of BVPS Unit 2 plant systems is not affected by this planned action. BVPS Unit 1 is not affected by this planned action.
"The NRC Resident Inspector has been notified."
* * * UPDATE AT 1736 EDT ON 6/29/07 FROM G. STOROLIS TO W. HUFFMAN * * *
The Radiation Monitor System Servers have been upgraded and returned to service and the Radiation Monitoring Information to the Emergency Response Data System (ERDS) and Safety Parameter Display System (SPDS) is now available and returned to service.
The licensee will notify the NRC Resident Inspector. R1DO (Powell) notified.
"The computer servers which supply radiation monitoring information to the ERDS (Emergency Response Data System) and SPDS (Safety Parameter Display System) systems will be taken out of service to implement a planned upgrade. The servers are being replaced with upgraded models and are expected to be out of service for approximately 4 to 8 hours. The ability of radiation monitors to alarm in the control room will be unavailable while the servers are being replaced. The in plant radiation monitoring skids will be unaffected, as will any automatic actions generated by the monitors. The safety related radiation monitor displays in the control room will also remain available. As a compensatory measure while both servers are unavailable, a dedicated radiation protection technician will monitor the in plant radiation monitor skids to update the control room if anomalous indications are observed. In addition, operations will record the safety related radiation monitor readings every 2 hours.
"This is an 8 hour reportable event per 10CFR50.72(b)(3)(xiii), Major Loss of Assessment Capability. The operations of BVPS Unit 2 plant systems is not affected by this planned action. BVPS Unit 1 is not affected by this planned action.
"The NRC Resident Inspector has been notified."
* * * UPDATE AT 1736 EDT ON 6/29/07 FROM G. STOROLIS TO W. HUFFMAN * * *
The Radiation Monitor System Servers have been upgraded and returned to service and the Radiation Monitoring Information to the Emergency Response Data System (ERDS) and Safety Parameter Display System (SPDS) is now available and returned to service.
The licensee will notify the NRC Resident Inspector. R1DO (Powell) notified.
General Information or Other
Event Number: 43469
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: CHRISTUS ST.FRANCIS CABRINI HOSPITAL
Region: 4
City: ALEXANDRIA State: LA
County:
License #: LA-1121-L01
Agreement: Y
Docket:
NRC Notified By: RICHARD PENROD
HQ OPS Officer: JASON KOZAL
Licensee: CHRISTUS ST.FRANCIS CABRINI HOSPITAL
Region: 4
City: ALEXANDRIA State: LA
County:
License #: LA-1121-L01
Agreement: Y
Docket:
NRC Notified By: RICHARD PENROD
HQ OPS Officer: JASON KOZAL
Notification Date: 07/03/2007
Notification Time: 09:29 [ET]
Event Date: 06/29/2007
Event Time: 00:00 [CDT]
Last Update Date: 07/03/2007
Notification Time: 09:29 [ET]
Event Date: 06/29/2007
Event Time: 00:00 [CDT]
Last Update Date: 07/03/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
MICHAEL SHANNON (R4)
MICHELE BURGESS (FSME)
MICHAEL SHANNON (R4)
MICHELE BURGESS (FSME)
AGREEMENT STATE REPORT - MEDICAL MISADMINISTRATION
"Christus St. Francis Cabrini hospital called and reported an over exposure on a treatment using an HDR [High Dose Rate system]. The HDR system delivered a dose 40% more than what the treatment plan called for to the patient. The overexposure for the treatment was reported as 1400 cGy. This is all of the information we have at this time. An investigation has started for this incident."
LA report number - LA070017
A "Medical Event" may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
"Christus St. Francis Cabrini hospital called and reported an over exposure on a treatment using an HDR [High Dose Rate system]. The HDR system delivered a dose 40% more than what the treatment plan called for to the patient. The overexposure for the treatment was reported as 1400 cGy. This is all of the information we have at this time. An investigation has started for this incident."
LA report number - LA070017
A "Medical Event" may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
General Information or Other
Event Number: 43460
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: STARMET NMI
Region: 1
City: CONCORD State: MA
County:
License #: SM-0179
Agreement: Y
Docket:
NRC Notified By: BRUCE PACKARD
HQ OPS Officer: JOHN KNOKE
Licensee: STARMET NMI
Region: 1
City: CONCORD State: MA
County:
License #: SM-0179
Agreement: Y
Docket:
NRC Notified By: BRUCE PACKARD
HQ OPS Officer: JOHN KNOKE
Notification Date: 06/29/2007
Notification Time: 13:38 [ET]
Event Date: 06/29/2007
Event Time: 11:00 [EDT]
Last Update Date: 07/05/2007
Notification Time: 13:38 [ET]
Event Date: 06/29/2007
Event Time: 11:00 [EDT]
Last Update Date: 07/05/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RAY POWELL (R1)
CINDY FLANNERY (FSME)
RAY POWELL (R1)
CINDY FLANNERY (FSME)
AGREEMENT STATE REPORT - CONTAMINATED AREA
The agreement state provided the following information via facsimile:
"During response to a fire, an on-site response personnel monitored area dose rates of 4 mrem/hour beta dose at waist level in an area about 20 meters east of building. On 06/29/07 Agency representatives and licensee confirmed area dose rates. Area was on pavement inside a fenced area. Caution tape was used to isolate the area. The licensee does not have regularly scheduled work hour on Friday, so the contract RSO said he will respond on Monday. This event does not appear to be related to the fire on-site [EN# 43447] because there is visible metallic contamination in the proximity of scrape-like tracks in the pavement. Suspected contaminate is DU."
Discovery date and time was 06/27/07 at 02:00 EDT.
* * * UPDATE AT 1008 EDT ON 7/5/07 FROM BRUCE PACKARD TO S. SANDIN VIA FAX * * *
The following information was provided as an update:
"On 7/2/07 contract RSO performed survey of the area. Licensee sealed the most active area with roof coating (thin non-fibrous roofing cement). Dose rates were reported to drop by a factor of 2. When the coat cures the licensee will add another coat.
"Rough calculation confirmed this spill is greater than 5 X 105 CMR 296 B values.
"Because Starmet was required to provide multiple agency access to this area as part of CERCLA cleanup, it is unlikely that the cause of the event or the responsible party will be identified."
Notified R1DO (Rogge) and FSME (Moore).
The agreement state provided the following information via facsimile:
"During response to a fire, an on-site response personnel monitored area dose rates of 4 mrem/hour beta dose at waist level in an area about 20 meters east of building. On 06/29/07 Agency representatives and licensee confirmed area dose rates. Area was on pavement inside a fenced area. Caution tape was used to isolate the area. The licensee does not have regularly scheduled work hour on Friday, so the contract RSO said he will respond on Monday. This event does not appear to be related to the fire on-site [EN# 43447] because there is visible metallic contamination in the proximity of scrape-like tracks in the pavement. Suspected contaminate is DU."
Discovery date and time was 06/27/07 at 02:00 EDT.
* * * UPDATE AT 1008 EDT ON 7/5/07 FROM BRUCE PACKARD TO S. SANDIN VIA FAX * * *
The following information was provided as an update:
"On 7/2/07 contract RSO performed survey of the area. Licensee sealed the most active area with roof coating (thin non-fibrous roofing cement). Dose rates were reported to drop by a factor of 2. When the coat cures the licensee will add another coat.
"Rough calculation confirmed this spill is greater than 5 X 105 CMR 296 B values.
"Because Starmet was required to provide multiple agency access to this area as part of CERCLA cleanup, it is unlikely that the cause of the event or the responsible party will be identified."
Notified R1DO (Rogge) and FSME (Moore).
General Information or Other
Event Number: 43461
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: NOT APPLICABLE
Region: 1
City: NORTH ANDOVER State: MA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JOHN SUMARES
HQ OPS Officer: BILL HUFFMAN
Licensee: NOT APPLICABLE
Region: 1
City: NORTH ANDOVER State: MA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JOHN SUMARES
HQ OPS Officer: BILL HUFFMAN
Notification Date: 06/29/2007
Notification Time: 14:23 [ET]
Event Date: 06/29/2007
Event Time: 00:00 [EDT]
Last Update Date: 06/29/2007
Notification Time: 14:23 [ET]
Event Date: 06/29/2007
Event Time: 00:00 [EDT]
Last Update Date: 06/29/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RAY POWELL (R1)
EDWIN HACKETT (FSME)
RAY POWELL (R1)
EDWIN HACKETT (FSME)
AGREEMENT STATE - MASSACHUSETTS - DEUTERIUM CONTAMINATED WITH TRITIUM RECEIVED BY NON-LICENSED BUSINESS
The agreement state provided the following information via facsimile:
"The Agency was informed by a non-licensed business, Cambridge Isotopes Laboratory of 50 Frontage Road, North Andover, MA, that a shipment of deuterium water received from a foreign vendor, Ontario Power Generation, was contaminated with Hydrogen-3. Upon a customer complaint, the business hired a consultant to analyze an aliquot from the original batch shipment and the aliquot has been determined to contain 20 millicuries per liter of tritium. The business has also notified their employees, the vendor from which the shipment originated, and three of the company's customers in the United States that received finished, and contaminated , product from the company. Bioassay procedures are being implemented and surveys are commencing to determine if personnel became contaminated or if the facility became contaminated."
This report has been assigned MA DPH / RCP docket # 06-7156.
The agreement state provided the following information via facsimile:
"The Agency was informed by a non-licensed business, Cambridge Isotopes Laboratory of 50 Frontage Road, North Andover, MA, that a shipment of deuterium water received from a foreign vendor, Ontario Power Generation, was contaminated with Hydrogen-3. Upon a customer complaint, the business hired a consultant to analyze an aliquot from the original batch shipment and the aliquot has been determined to contain 20 millicuries per liter of tritium. The business has also notified their employees, the vendor from which the shipment originated, and three of the company's customers in the United States that received finished, and contaminated , product from the company. Bioassay procedures are being implemented and surveys are commencing to determine if personnel became contaminated or if the facility became contaminated."
This report has been assigned MA DPH / RCP docket # 06-7156.
Power Reactor
Event Number: 43462
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: BILL HUFFMAN
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: BILL HUFFMAN
Notification Date: 06/29/2007
Notification Time: 20:45 [ET]
Event Date: 06/29/2007
Event Time: 17:52 [EDT]
Last Update Date: 06/29/2007
Notification Time: 20:45 [ET]
Event Date: 06/29/2007
Event Time: 17:52 [EDT]
Last Update Date: 06/29/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
BILL TRAVERS (R2)
JARED WERMIEL (NRR)
THOMAS BLOUNT (IRD)
MEL LEACH (DPR)
GENE GUTHRIE (R2)
BILL TRAVERS (R2)
JARED WERMIEL (NRR)
THOMAS BLOUNT (IRD)
MEL LEACH (DPR)
GENE GUTHRIE (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
REACTOR TRIP AND SPURIOUS SAFETY INJECTION
"At 1752 hours EDT Unit 2 received a 'B' train safety injection (SI). This spurious SI on 'B' train caused a trip of the main feedwater pumps and a turbine trip. The Unit 2 reactor tripped due to the turbine trip. The single train SI resulted in ECCS flow to the RCS. Both trains of SI were manually initiated per station procedures. The 'B' train of SI could not be reset and this resulted in RCS inventory increasing and lifting of the pressurizer PORV's. The pressurizer relief tank rupture disc ruptured and released water to the containment sump. SI flow to the core has been secured. Normal charging has been returned to service. This event is reportable per 10CFR50.72(b)(2)(iv)(A) for ECCS flow to the RCS. 10CFR50.72(b)(2)(iv)(B) for RCS Actuation (Rx/Turbine Trip). 10 CFR50.72(b)(3)(iv)(A) for AFW pump start, containment phase 'A' isolation, ECCS pumps actuation, and EDG starts. The AFW pump auto started during the event and operated as expected. Cause of the 'B' train SI is unknown at this time."
All rods fully inserted. All systems functioned as required with the exception of the 'B' train SI which spuriously actuated and then could not be reset. All equipment started as expected from the SI actuation. AFW is still supplying cooling water to the steam generators at this time and decay heat is being discharged via steam dumps to the condenser. The licensee does not yet know how much water was discharged to the containment sump. The reactor is currently stable at no-load temperature and pressure with the level in the pressurizer a little high but tracking down to normal.
The licensee notified the NRC Resident Inspector.
"At 1752 hours EDT Unit 2 received a 'B' train safety injection (SI). This spurious SI on 'B' train caused a trip of the main feedwater pumps and a turbine trip. The Unit 2 reactor tripped due to the turbine trip. The single train SI resulted in ECCS flow to the RCS. Both trains of SI were manually initiated per station procedures. The 'B' train of SI could not be reset and this resulted in RCS inventory increasing and lifting of the pressurizer PORV's. The pressurizer relief tank rupture disc ruptured and released water to the containment sump. SI flow to the core has been secured. Normal charging has been returned to service. This event is reportable per 10CFR50.72(b)(2)(iv)(A) for ECCS flow to the RCS. 10CFR50.72(b)(2)(iv)(B) for RCS Actuation (Rx/Turbine Trip). 10 CFR50.72(b)(3)(iv)(A) for AFW pump start, containment phase 'A' isolation, ECCS pumps actuation, and EDG starts. The AFW pump auto started during the event and operated as expected. Cause of the 'B' train SI is unknown at this time."
All rods fully inserted. All systems functioned as required with the exception of the 'B' train SI which spuriously actuated and then could not be reset. All equipment started as expected from the SI actuation. AFW is still supplying cooling water to the steam generators at this time and decay heat is being discharged via steam dumps to the condenser. The licensee does not yet know how much water was discharged to the containment sump. The reactor is currently stable at no-load temperature and pressure with the level in the pressurizer a little high but tracking down to normal.
The licensee notified the NRC Resident Inspector.
General Information or Other
Event Number: 43464
Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: ATL, INC
Region: 4
City: PHOENIX State: AZ
County:
License #: AZ 7-116
Agreement: Y
Docket:
NRC Notified By: AUBREY GODWIN
HQ OPS Officer: JEFF ROTTON
Licensee: ATL, INC
Region: 4
City: PHOENIX State: AZ
County:
License #: AZ 7-116
Agreement: Y
Docket:
NRC Notified By: AUBREY GODWIN
HQ OPS Officer: JEFF ROTTON
Notification Date: 07/02/2007
Notification Time: 11:49 [ET]
Event Date: 06/29/2007
Event Time: 00:00 [MST]
Last Update Date: 07/05/2007
Notification Time: 11:49 [ET]
Event Date: 06/29/2007
Event Time: 00:00 [MST]
Last Update Date: 07/05/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DALE POWERS (R4)
MICHELE BURGESS (FSME)
ILTAB (via email)
MEXICO (via fax)
DALE POWERS (R4)
MICHELE BURGESS (FSME)
ILTAB (via email)
MEXICO (via fax)
ARIZONA AGREEMENT STATE REPORT - STOLEN TROXLER MOISTURE DENSITY GAUGE
The State provided the following information via email:
"At approximately 4:00 PM June 29, 2007, the Agency [Arizona Radiation Regulatory Agency] was informed that the Licensee had a pickup truck stolen with a Troxler Model 3440 gauge, SN 35574. The theft occurred at approximately 2:40 PM when someone jumped into the truck, which was running while the employee loaded tools. The truck is a white 2006 Chevrolet. The Troxler gauge was locked in a 16 gauge steel tool box with a hardened and anti-theft designed lock and hasp. The steel box is bolted to the frame of the truck. The gauge contains 8 mCi of Cesium-137 and 40 mCi Am:Be-241.
"Phoenix PD is investigating and has issued report number 2007-71277015
"The Agency continues to investigate this event.
"The states of CA, NV, CO, UT, and NM, FBI, and Mexico are being notified of this event."
Arizona Event Number: 07-009
* * * UPDATE FROM AUBREY GODWIN TO JOE O'HARA VIA E-MAIL AT 1230 ON 7/5/07 * * *
"As of 4:00 PM July 3, 2007, the vehicle and device have been recovered. There is evidence the device was removed from the shipping container and the source possibly exposed. The Agency continues to investigate this event and the possible exposure of individuals.
"The states of CA, NV, CO, UT, and NM and Mexico and U.S. NRC and FBI are being notified of this event."
"Supplemental Notice: 07-009S."
Notified R4DO(Powers), FSME(Moore), Mexico (via e-mail) and ILTAB (via e-mail)
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks.
The State provided the following information via email:
"At approximately 4:00 PM June 29, 2007, the Agency [Arizona Radiation Regulatory Agency] was informed that the Licensee had a pickup truck stolen with a Troxler Model 3440 gauge, SN 35574. The theft occurred at approximately 2:40 PM when someone jumped into the truck, which was running while the employee loaded tools. The truck is a white 2006 Chevrolet. The Troxler gauge was locked in a 16 gauge steel tool box with a hardened and anti-theft designed lock and hasp. The steel box is bolted to the frame of the truck. The gauge contains 8 mCi of Cesium-137 and 40 mCi Am:Be-241.
"Phoenix PD is investigating and has issued report number 2007-71277015
"The Agency continues to investigate this event.
"The states of CA, NV, CO, UT, and NM, FBI, and Mexico are being notified of this event."
Arizona Event Number: 07-009
* * * UPDATE FROM AUBREY GODWIN TO JOE O'HARA VIA E-MAIL AT 1230 ON 7/5/07 * * *
"As of 4:00 PM July 3, 2007, the vehicle and device have been recovered. There is evidence the device was removed from the shipping container and the source possibly exposed. The Agency continues to investigate this event and the possible exposure of individuals.
"The states of CA, NV, CO, UT, and NM and Mexico and U.S. NRC and FBI are being notified of this event."
"Supplemental Notice: 07-009S."
Notified R4DO(Powers), FSME(Moore), Mexico (via e-mail) and ILTAB (via e-mail)
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks.